Event Notification Report for March 9, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
03/08/1999 - 03/09/1999
** EVENT NUMBERS **
35447 35448 35449 35450 35451
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|Power Reactor |Event Number: 35447 |
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| FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 03/08/1999|
| UNIT: [1] [] [] STATE: LA |NOTIFICATION TIME: 15:15[EST]|
| RXTYPE: [1] GE-6 |EVENT DATE: 03/08/1999|
+------------------------------------------------+EVENT TIME: 11:42[CST]|
| NRC NOTIFIED BY: GEORGE TURNER |LAST UPDATE DATE: 03/08/1999|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |GARY SANBORN R4 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 82 Power Operation |82 Power Operation |
| | |
| | |
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EVENT TEXT
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| INADVERTENT ACTUATION OF SINGLE OFFSITE SIREN DURING TESTING OF ACTUATION |
| SYSTEM |
| |
| During Y2K testing of the offsite siren actuation system, a single siren |
| actuated for about 5 seconds. The test was terminated and the system |
| returned to pretest conditions. The licensee notified the Louisiana Office |
| of Emergency Preparedness (LOEP) and informed them of the actuation. The |
| LOEP decided not to make a public announcement on the emergency alert system |
| as the siren was only actuated for a short period of time. |
| |
| The licensee notified the local parishes and the NRC Resident Inspector. |
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|General Information or Other |Event Number: 35448 |
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| REP ORG: FAIRBANKS MORSE ENGINE DIVISION |NOTIFICATION DATE: 03/08/1999|
|LICENSEE: FAIRBANKS MORSE ENGINE DIVISION |NOTIFICATION TIME: 15:29[EST]|
| CITY: BELOIT REGION: 3 |EVENT DATE: 03/08/1999|
| COUNTY: STATE: WI |EVENT TIME: 14:20[CST]|
|LICENSE#: AGREEMENT: N |LAST UPDATE DATE: 03/08/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |TOM MOSLAK R1 |
| |VERN HODGE (FAX) NRR |
+------------------------------------------------+RONALD GARDNER R3 |
| NRC NOTIFIED BY: JAMES GOLDING | |
| HQ OPS OFFICER: FANGIE JONES | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|CCCC 21.21 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| 10 CFR PART 21 REPORT REGARDING IMPROPER HEAT TREATMENT TO CAM ROLLERS |
| |
| On February 9, 1999, Coltec Industries, Fairbanks Morse Engine Division |
| (FMED), became aware of a |
| potential safety hazard associated with the air and exhaust valve cam |
| rollers for FM-ALCO 251 engines. Final analysis was completed on March 8, |
| 1999 by Engineering and Quality Assurance. They determined the cause to be |
| improper heat treatment of the cam rollers, which results in premature wear |
| of the roller and possible damage to the camshaft lobe, roller pin, and push |
| rod. The suspect rollers were induction hardened, which resulted in |
| inadequate case depth hardness and surface hardness. |
| |
| FMED had supplied the suspect rollers to Consolidated Edison Indian Point 2 |
| nuclear power station on November 14, 1997. Based on a review of FMED |
| records, Consolidated Edison is the only nuclear utility that is impacted. |
| |
| FMED has taken corrective action to prevent reoccurrence. In addition, the |
| tolerance used during the dedication process for the cam rollers has been |
| changed. Other tolerances will be reviewed as parts are dedicated. |
| |
| It should be noted that FMED has not been notified, nor is it aware of any |
| air and exhaust valve cam roller failures that have occurred at any nuclear |
| facilities. The failures that have occurred have been in commercial |
| applications after approximately 200 hours of operation. |
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|Power Reactor |Event Number: 35449 |
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| FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 03/08/1999|
| UNIT: [1] [2] [] STATE: MI |NOTIFICATION TIME: 16:53[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/08/1999|
+------------------------------------------------+EVENT TIME: 14:00[EST]|
| NRC NOTIFIED BY: MARY BETH GREENDONNER |LAST UPDATE DATE: 03/08/1999|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |RONALD GARDNER R3 |
|10 CFR SECTION: | |
|DDDD 73.71 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Cold Shutdown |0 Cold Shutdown |
|2 N N 0 Cold Shutdown |0 Cold Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| PLANT SECURITY REPORT |
| |
| Safeguards system degradation related to potential unauthorized entry into a |
| vital area. Immediate compensatory measures taken upon discovery. |
| |
| The licensee notified the NRC Resident Inspector. |
| |
| Refer to the HOO Log for additional details. |
| |
| * * * UPDATE AT 1838 EST ON 3/8/99 BY MARY BETH GREENDONNER TO FANGIE JONES |
| * * * |
| |
| Additional safeguards system degradation found during additional inspection |
| after initial report. Immediate compensatory measures taken upon |
| discovery. |
| |
| The licensee notified the NRC Resident Inspector. |
| |
| The NRC Operations Officer notified the R3DO (R. Gardner) and R3 IAT (James |
| Creed). |
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|Power Reactor |Event Number: 35450 |
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| FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 03/08/1999|
| UNIT: [] [2] [3] STATE: AL |NOTIFICATION TIME: 23:39[EST]|
| RXTYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 03/08/1999|
+------------------------------------------------+EVENT TIME: 21:42[CST]|
| NRC NOTIFIED BY: RAYMOND SWAFFORD |LAST UPDATE DATE: 03/09/1999|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CAUDLE JULIAN R2 |
|10 CFR SECTION: | |
|ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 96 Power Operation |94 Power Operation |
|3 N Y 100 Power Operation |98 Power Operation |
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EVENT TEXT
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| Two Trains of Standby Gas Treatment (SBGT) Inoperable - Shutdown Required |
| by Technical Specifications |
| |
| "At 2042, with both U2 & U3 in Mode 1, U2 coasting down at 3145 MWth, U3 |
| 100% 3458 MWth, U2 and U3 received alarms 'SBGT C RH [Relative Humidity] |
| TEMP HIGH' and 'SBGT C FLT [Filter] BANK HTR ELEM POWER LOST.' The system |
| engineer reported the supply breaker for C train SBGT tripped. C SBGT was |
| declared inoperable. B SBGT was already INOP due to scheduled maintenance. |
| With two trains of SBGT INOP, this resulted in entering TS LCO 3.0.3 on both |
| units immediately. At 2141, shutdown was initiated on both U2 and U3. |
| This is reportable as a 1 hour report to the NRC under 10 CFR |
| 50.72(b)(1)(i)(A), as 'The initiation of any nuclear plant shutdown required |
| by the plant's Technical Specification.' |
| |
| "Upon investigation by Engineering and Maintenance it was determined there |
| was a problem with SBGT switch. Tech Spec Requirement 3.3.A.1 allows |
| tripping of the logic of the inoperable flow switch and starting the |
| affected SBGT C. This action was completed and C SBGT was declared OPERABLE |
| and TS LCO 3.0.3 exited at 2237." |
| |
| The licensee informed the NRC resident inspector. |
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|Power Reactor |Event Number: 35451 |
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| FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 03/09/1999|
| UNIT: [1] [] [] STATE: PA |NOTIFICATION TIME: 05:55[EST]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 03/09/1999|
+------------------------------------------------+EVENT TIME: 02:21[EST]|
| NRC NOTIFIED BY: JOHN HUNTER |LAST UPDATE DATE: 03/09/1999|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |TOM MOSLAK R1 |
|10 CFR SECTION: | |
|AINB 50.72(b)(2)(iii)(B) POT RHR INOP | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| COMMON FAILURE EFFECTING BOTH TRAINS OF SHUTDOWN COOLING |
| |
| "On 3/9/99, at 0221 it was discovered that the Unit 1 shutdown cooling |
| valves HV-51-1F015A, HV-51-1F015B, and HV-51-1F08 could not be opened, if |
| plant conditions required, due to a failure in the isolation logic circuit |
| connectors. |
| |
| "This failure affected both shutdown cooling return valves and a common |
| suction valve which results in one failure effecting both trains of shutdown |
| cooling. The identified deficiency is being planned for repairs. This |
| condition, of a single failure disabling multiple trains of a system, is |
| being reported pursuant to 50.72(b)(2)(iii)." |
| |
| This deficiency was discovered during routine maintenance. These valves |
| could be opened manually using existing plant procedures if it were |
| necessary to initiate shutdown cooling. |
| |
| The licensee will notify the NRC resident inspector. |
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Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021